Eigenvalue sensitivity and nuclear data uncertainty analysis for the Moroccan TRIGA Mark II research reactor using SCALE6.2 and MCNP6.2

Sensitivity and uncertainty analysis on keff due to nuclear data in the KRITZ-2:19 – Comparison between JENDL-4.0 and ENDF/B-VII.1

(2019) Abdulaziz Ahmed et al.   ANNALS OF NUCLEAR ENERGY

Neutronic study of the 2-MW TRIGA MARK-II research reactor by the deterministic codes DRAGON5 & DONJON5

(2019) H. El Yaakoubi et al.   APPLIED RADIATION AND ISOTOPES

Nuclear data sensitivity and uncertainty analysis of critical VENUS-F cores with the Serpent Monte Carlo code

(2019) E. Fridman et al.   ANNALS OF NUCLEAR ENERGY

Computing eigenvalue sensitivity coefficients to nuclear data based on the CLUTCH method with RMC code

(2016) Yishu Qiu et al.   ANNALS OF NUCLEAR ENERGY

SCALE Continuous-Energy Eigenvalue Sensitivity Coefficient Calculations

(2016) Christopher M. Perfetti et al.   NUCLEAR SCIENCE AND ENGINEERING

Sensitivity and Uncertainty Analysis Capabilities and Data in SCALE

(2015) B. T. Rearden et al.   NUCLEAR TECHNOLOGY

Safety analysis and optimization of the core fuel reloading for the Moroccan TRIGA Mark-II reactor

(2013) B. Nacir et al.   ANNALS OF NUCLEAR ENERGY

Monte Carlo modelling of TRIGA research reactor

(2010) B. El Bakkari et al.   RADIATION PHYSICS AND CHEMISTRY